HEAVY WATER MODERATED POWER REACTORS. Progress Report, December 1962

Technical Report · Tue Jan 01 04:00:00 EST 1963

OSTI ID:4736223

Isakoff, L; Hood, R.R. comps.

BS>The Heavy Water Components Test Reactor (HWCTR) was operated intermittently for irradiation tests of fuel assemblies of various types. The U metal assembly that failed in the HWCTR in Nov. was removed to a spent fuel basin without difficulty. A one-week shutdown of the HWCTR was made for temporary repair of one of the steam generators to eliminate D/sub 2/O leakage through faulty tube sheet seal welds. Development was started on a fabrication process for coextruded driver fuel assemblies of the new two-tube design that is being considered for future use in the HWCTR. Fabrication was started on ten Zircaloy- clad tubes of U--350 ppm Fe--900 ppm Al for irradiation tests in the HWCTR; fabrication was completed on seven tubular assemblies of mechanical compacted uranium oxide, also scheduled for HWCTR tests. Preliminary evaluation tests were conducted on extruded joints of Zircaloy and stainless steel to obtain information on resistance to corrosion by water, and the effect of annealing on diffusion zone thickness and bond strength. (auth)

• Research Organization: Du Pont de Nemours (E.I.) & Co. Atomic Energy Div., Wilmington, Del.
• NSA Number: NSA-17-013672
• OSTI ID: 4736223
• Report Number(s): DP-815
• Country of Publication: United States
• Language: English

Related Subjects

ALUMINUM ALLOYS
ANNEALING
BONDING
COMPACTING
CONFIGURATION
CORROSION
DIFFUSION
EXTRUSION
FABRICATION
FAILURES
FUEL CANS
FUEL ELEMENTS
GENERATORS
HEAVY WATER MODERATOR
HWCTR
IRON ALLOYS
IRRADIATION
LEAKS
MAINTENANCE
OPERATION
POWER PLANTS
REACTOR TECHNOLOGY
REACTORS
REMOTE HANDLING
RESEARCH REACTORS
SEALS
STAINLESS STEELS
STEAM
TESTING
TUBES
URANIUM ALLOYS
URANIUM OXIDES
WELDING
ZIRCALOY